Search results for: U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Engineering
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61
Projecting labor demand and worker immigration at nuclear power plant construction sites : an evaluation of methodology
Authors: Herzog, H. W. (Henry W.)
Published: The Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; National Technical Information Service, 1981Physical Description: viii, 121 pages : illustrations ; 28 cmHoldings: Loading…
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62
Review of the natural circulation effect in the Vermont Yankee spent-fuel pool
Authors: Wheeler, C. L.
Published: Division of Engineering and Systems Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1988Physical Description: xxiii, 95, 29, 1 page : illustrations ; 28 cmHoldings: Loading…
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63
Evaluation of non-radiological water chemistry at power reactors
Authors: Banerjee, S.
Published: Division of Engineering and Systems Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1989Physical Description: 1 volume.Holdings: Loading…
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64
Experimental results pertaining to the performance of thermal igniters
Authors: Carmel, Michael K.
Published: Division of Engineering and Systems Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1989Physical Description: xi, 82 pages : illustrations ; 28 cmHoldings: Loading…
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65
A comparative analysis of special treatment requirements for systems, structures, and components (SSCs) of nuclear power plants with commercial requirements of non-nuclear power pl...
Authors: Phillips, J. H.
Published: Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 2002Physical Description: 1 volume., Also available via Internet from NRC web site. Address as of 05/22/03: http://www.nrc.gov/reading-rm/adams/web-based.html (image available through search screen); current access available via PURL.Holdings: Loading…AlternaTIFF viewer required (software available free) (Federal Depository Library Program Persistant URL)
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66
Control room habitability survey of licensed commercial nuclear power generating stations
Authors: Driscoll, J. W.
Published: Division of Engineering and System Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1988Physical Description: xiv, 255 pages : illustrations ; 28 cmHoldings: Loading…
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67
The application of fracture proof design methods using tearing instability theory to nuclear piping postulating circumferential through wall cracks
Authors: Paris, P. C. (Paul Croce), 1930-
Published: The Division, 1983Physical Description: xv, 190 pages : illustrations ; 28 cmHoldings: Loading…
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68
Seismic and dynamic qualification of safety related electrical and mechanical equipment
Authors: Subudhi, M.
Published: Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1986Physical Description: xi, 53 pages : illustrations ; 28 cmHoldings: Loading…
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69
Seismic hazard characterization of the eastern United States : comparative evaluation of the LLNL and EPRI studies
Authors: Bernreuter, D. L.
Published: Division of Engineering and System Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1987Physical Description: xxx, 259 pages : illustrations, maps ; 28 cmHoldings: Loading…
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70
Seismic hazard characterization of 69 nuclear plant sites east of the Rocky Mountains
Published: Division of Engineering and System Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1989Physical Description: volumes : illustrations, maps ; 28 cmHoldings: Loading…
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71
Independent seismic evaluation of the Diablo Canyon Unit 1 containment annulus structure and selected piping systems
Published: The Commission, 1982Physical Description: x, 165 pages : illustrations ; 28 cmHoldings: Loading…
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72
Distribution of Corbicula fluminea at nuclear facilities
Authors: Counts, Clement Lee
Published: Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1985Physical Description: viii, 79 pages : maps ; 28 cmHoldings: Loading…
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73
An Evaluation of stress corrosion crack growth in BWR piping systems
Published: Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1985Physical Description: x, 66 pages : illustrations ; 28 cmHoldings: Loading…
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74
Evaluation of current methodology employed in probabilistic risk assessment (PRA) of fire events at nuclear power plants
Authors: Ruger, C.
Published: Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regultory Commission, 1985Physical Description: vii, 37 pages ; 28 cmHoldings: Loading…
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75
Probability-based evaluation of selected fire protection features in nuclear power plants
Authors: Azarm, M.
Published: Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1985Physical Description: xiv, 73 pages, A-3 pages : illustrations ; 28 cmHoldings: Loading…
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76
Examples, clarifications, and guidance on preparing requests for relief from pump and valve inservice testing requirements
Authors: Ransom, C. B.
Published: Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1996Physical Description: 1 volume (various pagings) ; 28 cmHoldings: Loading…
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77
Aging assessment of safety-related fuses used in low- and medium-voltage applications in nuclear power plants
Authors: Lofaro, M.
Published: Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 2002Physical Description: xiii, 65 pages : illustrations.Holdings: Loading…
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78
Estimating the potential impacts of a nuclear reactor accident : methodology and case studies
Published: The Commission, 1982Physical Description: 125 pages ; 28 cmHoldings: Loading…
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79
Evaluation of available data for probabilistic risk assessments (PRA) of fire events at nuclear power plants
Published: Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1985Physical Description: ix, 38 pages, A-8, B-13 pages : illustrations ; 28 cmHoldings: Loading…
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80
Consideration of uncertainties in soil-structure interaction computations
Authors: Costantino, C. J. (Carl J.)
Published: Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1992Physical Description: xii, 125 pages : illustrations ; 28 cmHoldings: Loading…
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Related Subjects
Nuclear power plants
Nuclear reactors
Safety measures
Containment
Piping
Materials
Earthquake effects
Stress corrosion
Nuclear facilities
Fires and fire prevention
Fire extinction
Pressurized water reactors
Reliability
Steel
Computer programs
Equipment and supplies
Nuclear pressure vessels
Steam-boilers
Testing
Valves
Boiling water reactors
Combustion
Corrosion
Data processing
Hydrogen
Mathematical models
Probabilities
Climatic factors
Cooling ponds
Effect of radiation on